Cylindrical dispersion type fuel element swelling in nonuniform temperature and neutron fields

被引：0

作者：

LIKHACHEV YUI

机构：

来源：

| 1971年 / 39卷 / 01期

关键词：

URANIUM DIOXIDE;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Results of calculations of the axisymmetric swelling of dispersion type fuel cores having austenitic steel matrix and UO//2 grains in radially nonuniform temperature and neutron fields are presented. See also English translation in Sov At Energy v 30 n 1 Jan 1971 p 49-50

引用

页码：44 / 45

共 30 条

[21] Numerical investigation of temperature fields in the duct of uranium-graphite reactor with fuel elements of bush type
Cherepanov A.N.
Popov V.N.
Detsel A.E.
Aleksandrov A.B.
Drobyaz A.I.
Thermophysics and Aeromechanics, 2006, 13 (3) : 419 - 425
[22] MEASUREMENT OF URANIUM-235 CONTENT IN A SPENT MTR TYPE FUEL-ELEMENT USING DELAYED-NEUTRON YIELD TECHNIQUE
AUGUSTSON, RH
WEISBIN, CR
HENRY, CN
NUCLEAR TECHNOLOGY, 1972, 14 (02) : 197 - +
[23] Development of finite element analysis code SPOTBOW for prediction of local velocity and temperature fields around distorted fuel pin in LMFBR assemblies
Shimizu, T
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1996, 33 (05) : 429 - 438
[24] Experimental Investigations of the Characteristics of Heat-Exchange and Temperature Fields in the Channels and Fuel-Element Assemblies of Lead-Cooled Fast Reactors
Rachkov, V. I.
Sorokin, A. P.
Zhukov, A. V.
Kuzina, Yu. A.
Privezentsev, V. V.
ATOMIC ENERGY, 2015, 118 (05) : 307 - 317
[25] Experimental Investigations of the Characteristics of Heat-Exchange and Temperature Fields in the Channels and Fuel-Element Assemblies of Lead-Cooled Fast Reactors
V. I. Rachkov
A. P. Sorokin
A. V. Zhukov
Yu. A. Kuzina
V. V. Privezentsev
Atomic Energy, 2015, 118 : 307 - 317
[26] Investigation of dog-boning & fishtailing defects in plate type dispersion fuel Rolling: Insights from finite element analysis and defect minimization techniques
Roy, Vikram
Sharma, Avaneesh
NUCLEAR ENGINEERING AND DESIGN, 2023, 414
[27] CROSS-FLOW CHARACTERISTICS OF FLANGE TYPE FUEL-ELEMENT FOR VERY HIGH-TEMPERATURE GAS-COOLED REACTOR
TAKIZUKA, T
KABURAKI, H
NAKAMURA, M
SUZUKI, K
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1987, 29 (12): : 1116 - 1126
[28] EFFECTIVE COOLANT FLOW-RATE OF FLANGE TYPE FUEL-ELEMENT FOR VERY HIGH-TEMPERATURE GAS-COOLED REACTOR
FUMIZAWA, M
SUZUKI, K
MURAKAMI, T
HAYAKAWA, H
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1989, 31 (07): : 828 - 836
[29] A MATHEMATICAL-MODEL FOR RADIATION EXCHANGE OF FUEL-FIRED FURNACE CHAMBERS AND ITS APPLICATION TO CALCULATE TEMPERATURE-FIELDS IN PUSHER TYPE FURNACES
STRACKE, H
KOHNE, H
STAHL UND EISEN, 1980, 100 (16): : 887 - 893
[30] Finite element analysis of temperature and stress fields of belt-type apparatus and preliminary studies on numerical simulation of steel-strip winding model
School of Mechanical Engineering, University of Jinan, Jinan 250022, China
Rengong Jingti Xuebao, 2008, 2 (493-499):

← 1 2 3 →